MCNP-PoliMi Calculations of Active Neutron Interrogation Measurements of HEU Metal
- ORNL
This paper presents a comparison of Monte Carlo Code/MCNP-PoliMi calculations [Ref 1] with measurements of the prompt neutron time behavior after introduction into the highly enriched uranium ({approx}93 wt % {sup 235}U) metal of interrogating neutrons from a time tagged {sup 252}Cf spontaneous fission source or a time and directionally tagged neutrons from a steady state DT neutron generator with an embedded alpha detector [Ref 2]. These measurements used a fast time correlation processor from the nuclear material identification system (NMIS) which measured the time distribution of detection events on a nanosecond time scale (equivalent to a randomly pulsed neutron measurement) and the time distribution of events in one detector after an event in another detector (equivalent to a two-detector Rossi-alpha measurement) [Ref 3]. These calculations of the prompt neutron time behavior were performed to verify the ability of calculational methods and cross sections to predict the results for subcritical experiments.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- DE-AC05-00OR22725
- OSTI ID:
- 988201
- Resource Relation:
- Conference: ANS 2008 Annual Meeting, Anaheim, CA, USA, 20080608, 20080612
- Country of Publication:
- United States
- Language:
- English
Similar Records
Preliminary MCNP-POLIMI Simulations for the Evaluation of the ''Floor Effect'': Comparison of APSTNG and Cf Sources
Subcritical Measurements Multiple HEU Metal Castings